Overview of plasma–material interaction experiments on EAST employing MAPES

Component development for operation in a large-scale fusion device requires thorough testing and qualification for the intended operational conditions. In particular environments are necessary which are comparable to the real operation conditions, allowing at the same time for in situ/in vacuo diagnostics and flexible operation, even beyond design limits during the testing. Various electron and neutral particle devices provide the capabilities for high heat load tests, suited for material samples and components from lab-scale dimensions up to full-size parts, containing toxic materials like beryllium, and being activated by neutron irradiation. To simulate the conditions specific to a fusion plasma both at the first wall and in the divertor of fusion devices, linear plasma devices allow for a test of erosion and hydrogen isotope recycling behavior under well-defined and controlled conditions. Finally, the complex conditions in a fusion device (including the effects caused by magnetic fields) are exploited for component and material tests by exposing test mock-ups or material samples to a fusion plasma by manipulator systems. They allow for easy exchange of test pieces in a tokamak or stellarator device, without opening the vessel. Such a chain of test devices and qualification procedures is required for the development of plasma-facing components which then can be successfully operated in future fusion power devices. The various available as well as newly planned devices and test stands, together with their specific capabilities, are presented in this manuscript. Results from experimental programs on test facilities illustrate their significance for the qualification of plasma-facing materials and components. An extended set of references provides access to the current status of material and component testing capabilities in the international fusion programs.

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“…For the EAST tokamak a mid-plane manipulator system is routinely used to expose materials to the plasma [205].…”

Section: Materials Tests In Tokamaksmentioning

confidence: 99%

“…the divertor manipulator in ASDEX Upgrade [182,333,334]. Retention-related PWI studies were also performed in the MAPES facility at EAST, with a focus on retention of fuel by means of co-deposition in gaps [205].…”

Section: Deposition and Retentionmentioning

confidence: 99%

Material testing facilities and programs for plasma-facing component testing

et al. 2017

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“…These parameters are similar to those of the EAST tokamak, which is upgrading its upper divertor to W and the researchers will focus on the investigation of fuel retention in the W gaps. [24] Although the fuel retention is not a very crucial problem for EAST because no tritium is used, the present work focuses on finding the parameter dependence of fuel retention inside the W divertor tiles. The parameters for the fuel retention inside the W in Eqs.…”

Section: Resultsmentioning

confidence: 99%

Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

Sang¹,

Dai²,

Sun³

et al. 2014

Chinese Phys. B

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“…The sustained plasma burning is a key step on the necessary scientific critical path toward fusion energy, for which, the transport of impurity should be well investigated. In the recent years, techniques such as optical spectrum [2], numerical simulation [3], ex-situ measurements [4,5], laser-induced breakdown spectroscopy [6] and Accelerator-based In-situ Materials Surveillance (AIMS) [7] have been applied to study the impurity transport in plasma. In order to figure out the dynamic impurity transport on the first wall of HL-2A/2M tokamak, Southwestern Institute of Physics is developing a deuteron RFQ accelerator as a part of the in-situ ion-beam diagnostic for material, and the RFQ group in Peking University is partnering in the design of the RFQ accelerator.…”

Section: Introductionmentioning

confidence: 99%

“…In order to meet the beam requirements, we have designed a room-temperature RFQ, operating at 162. 5 MHz, which has the ability to accelerate 10-mA deuteron beam up to 1.5 MeV with a duty factor of 1%. The conventional four-vane structure was adopted to provide high shunt impendence with low power losses.…”

Section: Introductionmentioning

confidence: 99%

RF design and tuning of a deuteron RFQ for detecting impurity deposition on a tokamak

Liu¹,

Bai²,

Wei³

et al. 2022

J. Inst.

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Peking University and Southwestern Institute of Physics are jointly developing a new deuteron Radio Frequency Quadrupole (RFQ) accelerator to study the migration and deposition of impurities on the first wall of a tokamak facility. The RFQ operates at 162.5 MHz with the duty factor of 1%, which can accelerate 10 mA deuteron beam from 40 keV up to 1.5 MeV within 2.2 m length. Such four-vane RFQ is divided into two segments and equipped with 40 tuners in total. In the electromagnetic (EM) design, the dipole stabilizer rods (DSRs) were optimized to obtain a mode separation of 3.1 MHz. The tuners and undercuts were also designed and optimized to fulfill the requirements of the resonant frequency, flat longitudinal field distribution and field tuning. Following the EM design, multi-physics analysis and structure error analysis was carried out. The cavity was fabricated with 99.9% oxygen-free electronic (OFE) copper. The assembly and braze of each RFQ module have been completed, the results of metrological measurements via coordinate measuring machine (CMM) indicate that there was no unexpected deformation. The intrinsic Q-value of the whole cavity is 12834 in the low level radio frequency (RF) measurements, which is 87% of the theoretical simulation with electrical conductivity of 5.8 × 107 S/m. After tuning, the quadrupole perturbative component decreased from 2.6% to 0.6%, and the dipole perturbative components decreased from 6.1% to 1%.

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Overview of plasma–material interaction experiments on EAST employing MAPES

Cited by 28 publications

References 22 publications

Material testing facilities and programs for plasma-facing component testing

Material testing facilities and programs for plasma-facing component testing

Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

RF design and tuning of a deuteron RFQ for detecting impurity deposition on a tokamak

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